• 反应堆工程 •

### 基于CFD方法的核动力系统热工安全特性研究进展

1. 西安交通大学 核科学与技术学院，陕西 西安710049；西安交通大学 陕西省先进核能技术重点实验室，陕西 西安710049
• 出版日期:2019-10-20 发布日期:2019-10-20

### Review on Safety Characteristic Research Progress of Nuclear Power Plant Thermal-hydraulics Using CFD Method

TIAN Wenxi;WANG Mingjun;QIU Suizheng;SU Guanghui

1. School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, China; Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, Xi’an Jiaotong University, Xi’an 710049, China
• Online:2019-10-20 Published:2019-10-20

Abstract:

Xi’an Jiaotong University Nuclear Thermal-hydraulic Laboratory (XJTU-NuTheL) has been committed to the development and application of high-precision thermal-hydraulic models of nuclear power plant based on CFD method. In recent years, series of research achievements in various nuclear engineering fields including single-phase CFD application, two-phase CFD model development, large eddy simulation (LES) and direct numerical simulation (DNS), were accomplished in XJTU-NuTheL. The three-dimensional porous media thermal-hydraulic models for key equipments thermal hydraulic study in the nuclear power plant such as reactor pressurized vessel, steam generator and passive residual heat exchanger were developed. The mathematical models of complicate two-phase phenomena and ocean moving conditions were established. Also, with the high fidelity simulation requirement of the whole reactor system, the nuclear reactor system multi-dimensional and multi-physics coupling platforms were developed based on CFD codes. In this paper, the latest achievements on the nuclear reactor thermal-hydraulic research using CFD method at XJTU-NuTheL were introduced and described. In addition, the major challenges and promising directions of CFD applications on the nuclear reactor engineering field were proposed, which would be beneficial for the promotion of its further application.